Radioactive drug administration device and radioactive drug measurement method

Abstract

The present invention provides a radioactive drug administration device and a radioactive drug administration method that can easily and accurately determine the yield of the radioactive drug solution contained in a containment container. [Solution] According to the radioactive drug dispensing device 1, a sensor 80 for measuring the yield of radioactive drug in vial 6 is provided at the bottom of the shield case 15 in which vial 6 is placed. The sensor 80 can measure the yield of radioactive drug in vial 6 while vial 6 remains in the shield case 15. Therefore, the sensor 80 can easily measure while suppressing the influence of external radiation by the shield case 15. Furthermore, even if the amount of radioactive drug in vial 6 decreases, the liquid level fluctuates, but the radioactive drug remains accumulated on the bottom surface 76b side of vial 6. By measuring from the bottom of the shield case 15, the sensor 80 can perform measurements while suppressing the influence of geometric changes in the object being measured.

Description

Technical Field

[0001] The present invention relates to a radioactive liquid medicine administration device and a radioactive liquid medicine measurement method.

Background Art

[0002] Conventionally, as a technique in this field, a radioactive liquid medicine administration device described in Patent Document 1 below is known. In this device, a transport line for transporting a transport liquid connects a transport liquid syringe and a needle with wings. A liquid medicine line for supplying a radioactive liquid medicine merges with this transport line. After a radioactive liquid medicine having a desired radiation dose is sent from a liquid medicine syringe into the transport line through the liquid medicine line, it is pushed out by the transport liquid syringe together with the transport liquid, and the radioactive liquid medicine is administered to a patient through the transport line and the needle with wings. The above transport line and the like are connected using a pinch valve or the like.

Prior Art Documents

Patent Documents

[0003]

Patent Document 1

Summary of the Invention

Problems to be Solved by the Invention

[0004] In the above radioactive liquid medicine administration device, the amount of the radioactive liquid medicine could not be grasped while it was stored in the storage container. Therefore, since the amount of the radioactive liquid medicine could not be accurately grasped, problems such as insufficient dosage could occur during the administration of the radioactive liquid medicine. Therefore, it has been required to easily and accurately grasp the amount of the radioactive liquid medicine stored in the storage container.

[0005] The present invention has been made in view of the above, and an object thereof is to provide a radioactive liquid medicine administration device and a radioactive liquid medicine administration method capable of easily and accurately grasping the amount of the radioactive liquid medicine stored in a storage container. [Means for solving the problem]

[0006] To achieve the above objective, a radioactive drug administration device according to one embodiment of the present invention comprises a container for containing a radioactive drug solution and a syringe for aspirating the radioactive drug solution from the container and discharging the radioactive drug solution for administration, wherein a sensor for measuring the yield of the radioactive drug solution in the container is provided at the bottom of the shield case in which the container is placed.

[0007] According to the radioactive drug dispensing device described above, a sensor for measuring the yield of the radioactive drug in the containment container is installed at the bottom of the shielding case in which the containment container is placed. Therefore, the sensor can measure the yield of the radioactive drug in the containment container while the container remains in the shielding case. Thus, the sensor can easily take measurements while suppressing the effects of external radiation by the shielding case. Furthermore, even if the amount of radioactive drug in the containment container decreases, the liquid level fluctuates, but the radioactive drug remains accumulated at the bottom of the containment container. Therefore, by measuring from the bottom of the shielding case, the sensor can perform measurements while suppressing the effects of geometric changes in the object being measured. As a result, the yield of the radioactive drug contained in the containment container can be easily and accurately determined.

[0008] The sensor may measure the yield of the radioactive liquid through a pinhole in the shielding case. In this case, the radiation from the containment container toward the sensor passes through the pinhole in the shielding case, suppressing the influence of external radiation, and is accurately directed toward the sensor in a small amount. Therefore, geometric variations in the measurement target can be suppressed.

[0009] A sliding mechanism is provided at the bottom of the shield case, allowing the containment container to slide relative to the radioactive drug delivery device, and the sensor may be fixed to the radioactive drug delivery device. In this case, once the containment container has been moved to the measurement position by the sliding mechanism, the sensor can perform the measurement.

[0010] The top of the sensor may be covered with a protective component. In this case, even if the sensor is placed at the bottom of the containment container, the sensor can be protected from contamination from above by the protective component.

[0011] A radioactive drug administration method according to one embodiment of the present invention is a radioactive drug administration device comprising a container for containing a radioactive drug and a syringe for aspirating the radioactive drug from the container and discharging the radioactive drug for administration, wherein the method for measuring the yield of the radioactive drug in the container is a method for measuring the yield by measuring the yield from the bottom of a shield case in which the container is placed.

[0012] This method of administering radioactive liquid can achieve the same effects and actions as the radioactive liquid administration device described above. [Effects of the Invention]

[0013] According to the present invention, it is possible to provide a radioactive drug administration device and a radioactive drug administration method that can easily and accurately determine the yield of the radioactive drug solution contained in a containment container. [Brief explanation of the drawing]

[0014] [Figure 1] This figure schematically illustrates the radioactive drug administration device according to the present invention. [Figure 2] This is a cross-sectional view showing the RI syringe, the first detection unit, and the second detection unit. [Figure 3] This is a cross-sectional view along line III-III in Figure 2. [Figure 4] This figure shows a table that correlates the volume of the radioactive liquid with the output values ​​detected by the first, second, and third RI sensors. [Figure 5] It is a graph corresponding to FIG. 4, where (a) shows the detection result of the first RI sensor, (b) shows the detection result of the second RI sensor, (c) shows the detection result of the third RI sensor, and (d) shows the average of the output values detected by the first to third RI sensors. [Figure 6] It is a flowchart showing the procedure of the first administration process. [Figure 7] It is a flowchart showing the procedure of the second administration process. [Figure 8] It is a plan view showing the container housing structure 100 which is the structure around the vial 6. [Figure 9] It is a side view of the container housing structure.

Embodiments for Carrying Out the Invention

[0015] Hereinafter, embodiments for carrying out the present invention will be described in detail with reference to the accompanying drawings. In the description of the drawings, the same reference numerals are assigned to the same elements, and redundant descriptions are omitted.

[0016] FIG. 1 is a diagram showing a radioactive drug solution administration device according to the present invention. As shown in FIG. 1, the radioactive drug solution administration device 1 includes a raw food line 7 connecting a raw food pack 3 containing physiological saline (or distilled water for injection) and a winged needle 5, a drug solution line 9 connecting a vial (storage container) 6 containing a radioactive drug solution and the raw food line 7, and a waste liquid line 11 connecting a waste liquid bottle 10 and the raw food line 7. The main part of the radioactive drug solution administration device 1 except the winged needle 5 is housed in a housing 13. The vial 6 is housed in a shield case 15 that shields radiation, and further, the shield case 15 is arranged in a first shield room 16. Also, the main part of the drug solution line 9 is arranged in a second shield room 17, and the waste liquid bottle 10 is arranged in a third shield room 18.

[0017] The raw food line 7 includes a first tube 19A, a second tube 19B, a third tube 19C, and a fourth tube 19D that transfer physiological saline for dilution or the like from the raw food pack 3 to the winged needle 5. The first tube 19A, the second tube 19B, the third tube 19C, and the fourth tube 19D are each composed of a sterilized extension tube. An injection needle 20 connected to the raw food pack 3 is provided at the proximal end of the first tube 19A. Also, a winged needle 5 for administering a radioactive drug solution to a subject is provided at the distal end of the fourth tube 19D.

[0018] The first tube 19A and the second tube 19B are connected via a first T-shaped tube 21. The first T-shaped tube 21 is provided with a first check valve 21a for preventing physiological saline or the like from flowing back into the first tube 19A. Also, the second tube 19B and the third tube 19C are connected via a second T-shaped tube 23, and the second T-shaped tube 23 is provided with a second check valve 23a for preventing physiological saline or the like from flowing back into the second tube 19B. Also, the third tube 19C and the fourth tube 19D are connected via a third T-shaped tube 25. A passage sensor 26 for detecting the passage of the radioactive drug solution through the fourth tube 19D is provided near the fourth tube 19D.

[0019] A raw food syringe 27 is connected to the branch portion of the first T-shaped tube 21. For example, a syringe driving device (not shown) by a pulse motor is connected to the raw food syringe 27. The raw food syringe 27 has a pusher portion movable by the drive of the syringe driving device, and pushes the physiological saline or the like in the first tube 19A into the second tube 19B, the third tube 19C, and the fourth tube 19D.

[0020] As shown in Figures 1 to 3, the drug solution line 9 includes a drug solution tube 29 for transferring the radioactive drug solution dispensed from the vial 6, an RI syringe 31 for aspirating the radioactive drug solution from the vial 6 via the drug solution tube 29 and discharging the aspirated radioactive drug solution into the saline solution line 7 for administration, an actuator 33 for moving the RI syringe 31, and a control means 35 for controlling the drive of the actuator 33. Furthermore, the drug solution line 9 includes a first detection unit (detection means) 37 and a second detection unit (auxiliary detection means) 39 for detecting the radioactivity intensity of the radioactive drug solution aspirated by the RI syringe 31.

[0021] Vial 6 contains a radioactive drug solution, such as FDG (2-deoxy-18Ffluoro-glucose), used in PET (positron emission tomography), at a concentration of approximately 500 mCi / 20 ml to 1 Ci / 20 ml. The drug solution tube 29 is an extension tube, and a catheter needle, which is inserted into vial 6, is provided at the base end of drug solution tube 29. The tip of drug solution tube 29 is connected to the first conduit 41a of the three-way branch pipe 41. The first conduit 41a is equipped with a drug solution check valve 41b to prevent backflow of the radioactive drug solution into vial 6.

[0022] The second conduit 41c of the three-way branch pipe 41 is connected to the branch of the second T-shaped pipe 23 of the saline line 7. Furthermore, the second conduit 41c is equipped with a saline check valve 41d to prevent the entry of physiological saline solution, etc.

[0023] The third conduit 41f of the three-way branch pipe 41 is connected to the RI syringe 31. The RI syringe 31 comprises an outer cylinder portion (tube portion) 31a and a plunger portion (piston portion) 31b that slides within the outer cylinder portion 31a. The tip of the outer cylinder portion 31a is provided with an intake / exhaust port 31c that communicates with the third conduit 41f, and a flange 31d is provided at the base end. The outer cylinder portion 31a is housed in a holder portion 43. The holder portion 43 is provided with a retaining bracket 43a formed so that the flange 31d is inserted into it. The outer cylinder portion 31a is prevented from coming off by the flange 31d being held in place by the retaining bracket 43a. By moving the plunger portion 31b, radioactive liquid is drawn into the outer cylinder portion 31a, and the drawn-in radioactive liquid is discharged.

[0024] The actuator 33 consists of a pulse motor and has a movable bracket 33a. The plunger portion 31b of the RI syringe 31 is fixed to the movable bracket 33a. The actuator 33 reciprocates the movable bracket 33a, thereby reciprocating the plunger portion 31b. The suction and discharge means 45 is composed of the RI syringe 31 and the actuator 33.

[0025] A control means 35 is connected to the actuator 33. The control means 35 corresponds to a PC (Personal Computer), and is composed of hardware such as a CPU (Central Processing Unit) and memory, and is connected to the actuator 33 to send and receive electrical signals. The control means 35 controls the aspiration for dispensing and discharge for administration of the radioactive drug solution by the RI syringe 31 by controlling the drive of the actuator 33. The control means 35 is also connected to the first detection unit 37 and the second detection unit 39, and can receive output values ​​output from the first detection unit 37 or the second detection unit 39.

[0026] A first detection unit 37 and a second detection unit 39 are provided on the outside of the holder portion 43 that holds the RI syringe 31, along the outer cylinder portion 31a of the RI syringe 31. The first detection unit 37 and the second detection unit 39 are positioned opposite each other, sandwiching the RI syringe 31. The first detection unit 37 is provided to determine the amount of radioactive drug solution drawn in by the RI syringe 31, and the second detection unit 39 is provided to monitor the first detection unit 37 and determine whether or not to administer the drug.

[0027] The first detection unit 37 is equipped with a first RI sensor 47A, a second RI sensor 47B, and a third RI sensor 47C. RI (Radioisotope) is an isotope that emits radiation and changes (decays) into other types of atomic nuclei. The first RI sensor 47A is a sensor that detects the decay rate (Bq) per second, i.e., the radioactivity intensity, and outputs it as an electrical signal. The second RI sensor 47B and the third RI sensor 47C function similarly. The first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C each independently detect the radioactivity intensity of the radioactive liquid stored in the outer cylinder 31a of the RI syringe 31.

[0028] The detection accuracy of the first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C increases as they are moved closer to the outer cylinder portion 31a, but the range in which they can be accurately detected narrows. Therefore, the first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C are arranged vertically along the axis L of the outer cylinder portion 31a, with the first RI sensor 47A positioned closer to the tip, the second RI sensor 47B closer to the center, and the third RI sensor 47C closer to the base. This arrangement makes it easier to bring each of the first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C closer to the outer cylinder portion 31a, thereby improving detection accuracy over a wide range along the axis L of the outer cylinder portion 31a.

[0029] The detection accuracy of the first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C increases as they are moved closer to the outer cylinder portion 31a, but the range in which they can be accurately detected narrows. Therefore, the first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C are arranged vertically along the axis L of the outer cylinder portion 31a, with the first RI sensor 47A positioned closer to the tip, the second RI sensor 47B closer to the center, and the third RI sensor 47C closer to the base. This arrangement makes it easier to bring each of the first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C closer to the outer cylinder portion 31a, thereby improving detection accuracy over a wide range along the axis L of the outer cylinder portion 31a. The details will be explained below with reference to Figures 4 and 5.

[0030] Figure 4 is a table showing the output values ​​(mV) and average values ​​(mV) when a predetermined liquid volume corresponding to a radioactivity intensity of 100 (MBq) is drawn up with the RI syringe 31, and detected independently by the first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C. Furthermore, in Figure 4, the predetermined liquid volumes corresponding to a radioactivity intensity of 100 (MBq) are shown as 0.2 (ml), 1.1 (ml), 2.1 (ml), 3 (ml), 4 (ml), and 5 (ml).

[0031] Figure 5 is a graph corresponding to Figure 4, with the liquid volume (ml) on the horizontal axis and the output value (mV) on the vertical axis. Furthermore, Figure 5(a) shows the detection results of the first RI sensor 47A, (b) shows the detection results of the second RI sensor 47B, (c) shows the detection results of the third RI sensor 47C, and (d) shows the average values ​​of the output values ​​(mV) detected by the first RI sensor 47A, second RI sensor 47B, and third RI sensor 47C for each liquid volume.

[0032] As shown in Figures 4 and 5(a), when the volume of the radioactive liquid is 0.2 ml and the radioactivity is 100 MBq, the radioactivity concentration is very high, and the output value of the first RI sensor 47A is 50 mV. However, when the radioactivity concentration of the radioactive liquid decreases and the volume increases, the output value of the first RI sensor 47A decreases. For example, when the volume of the radioactive liquid is 5 ml, the output value is 26 mV. Thus, when attempting to detect with the first RI sensor 47A alone, the output value varies depending on the volume of the radioactive liquid. Similarly, with the second RI sensor 47B (see Figure 5(b)), the output value is highest at 43 mV when the volume of liquid that reaches 100 MBq is 3 ml, and lowest at 34 mV when the volume is 0.2 ml. Furthermore, with the third RI sensor 47C (see Figure 5(c)), the output value is highest at 34 mV when the liquid volume that produces a radioactivity intensity of 100 MBq is 5 ml, and lowest at 15 mV when the liquid volume is 0.2 ml. Thus, even when the liquid volume that produces the same radioactivity intensity of 100 MBq is used for each of the first RI sensor 47A, second RI sensor 47B, and third RI sensor 47C individually is used, the output value varies depending on the liquid volume.

[0033] On the other hand, the average value of the output values ​​for 0.2 ml in the first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C is 33.0 mV. Similarly, the average value of the output values ​​for 1.1 ml is 34.0 mV, the average value of the output values ​​for 2.1 ml is 34.7 mV, the average value of the output values ​​for 3 ml is 35.0 mV, the average value of the output values ​​for 4 ml is 34.7 mV, and the average value of the output values ​​for 5 ml is 34.7 mV. In this way, the average values ​​of the output values ​​for the first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C show almost no variation due to the liquid volume, and are no longer affected by the volume of the radioactive liquid, thereby improving the detection accuracy of radioactivity intensity. As a result, the detection accuracy can be improved over a wide range along the axis of the outer cylinder 31a.

[0034] Furthermore, as shown in Figure 4, the overall average of the output values ​​corresponding to each liquid volume in the case of a radioactivity intensity of 100 MBq is 34.3 mV, with a standard deviation of 0.7. In this embodiment, when a radioactivity intensity of 100 MBq is administered to a subject, the overall average of the output values, 34.3 mV, is set as the target value. Note that as the radioactivity intensity administered to the subject increases, the output values ​​of the first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C also increase, so the output value set as the target value increases, and as the radioactivity intensity administered to the subject decreases, the output value set as the target value decreases.

[0035] As shown in Figures 2 and 3, the first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C are housed in a lead-based first shield chamber (shielding section) 49. The first shield chamber 49 has a first opening 49a through which radiation passes, on the side facing the outer cylinder section 31a, with the holder section 43 in between. The radioactivity intensity from the radioactive liquid stored in the outer cylinder section 31a is detected from the radiation passing through the first opening 49a of the first shield chamber 49. Other radiation is shielded by the first shield chamber 49. As a result, it becomes difficult for noise radiation to enter the first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C, improving the detection accuracy of the radioactivity intensity from the radioactive liquid stored in the outer cylinder section 31a. The shape and wall thickness of the first shield chamber 49 can be determined as appropriate. For example, the wall thickness around the first RI sensor 47A, which is close to the chemical solution tube 29 through which the radioactive liquid flows, can be made thicker than that around the second RI sensor 47B and the third RI sensor 47C, thereby making it less susceptible to noise interference.

[0036] The second detection unit 39 includes a fourth RI sensor 47D, a fifth RI sensor 47E, and a sixth RI sensor 47F arranged along the axis L of the outer cylinder portion 31a. The fourth RI sensor 47D, the fifth RI sensor 47E, and the sixth RI sensor 47F are housed in a second shielding chamber 51 made of lead. The second shielding chamber 51 has a second opening 51a formed on the side facing the outer cylinder portion 31a, with the holder portion 43 in between, through which radiation passes. The fourth RI sensor 47D, the fifth RI sensor 47E, and the sixth RI sensor 47F have the same configuration as the first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C, so their description is omitted. Also, the second shielding chamber 51 has the same configuration as the first shielding chamber 49, so their description is omitted.

[0037] As shown in Figure 1, the waste liquid line 11 includes a waste liquid tube 53 made of an extension tube, and the waste liquid tube 53 is connected to the waste liquid bottle 10 via a waste liquid pipe 55. The waste liquid tube 53 and the fourth tube 19D of the saline line 7 are provided with a first pinch valve 56A and a second pinch valve 56B, respectively. When the radioactive drug solution is administered, the first pinch valve 56A opens and the second pinch valve 56B closes, and when the radioactive drug solution is disposed of, the first pinch valve 56A closes and the second pinch valve 56B opens.

[0038] Next, the method of administering the radioactive drug solution using the radioactive drug solution administration device 1 will be explained with reference to Figure 6 or Figure 7. Figure 6 is a flowchart showing the procedure for the first administration process, where steps are abbreviated as S. Figure 7 is a flowchart showing the procedure for the second administration process, where steps are abbreviated as S. First, the method of administering the radioactive drug solution according to the procedure for the first administration process will be explained with reference to Figure 6.

[0039] As shown in Figure 6, when the first administration procedure is started, preparation is performed first, filling the first tube 19A, second tube 19B, third tube 19C, and fourth tube 19D of the saline line 7 with physiological saline, and filling the drug solution tube 29 of the drug solution line 9 with radioactive drug solution (Step 1).

[0040] Next, the operator operates an operating device (not shown) to set and input the target value of the radioactivity intensity to be administered to the subject. The data input via the operating device is input to the control device 35, which stores the target value in memory (Step 2).

[0041] Subsequently, the control means 35 drives the actuator 33 to begin aspirating the radioactive liquid with the RI syringe 31 and storing the radioactive liquid in the outer cylinder portion 31a (step 3). The first detection unit 37 also detects the radioactivity intensity of the radioactive liquid stored in the outer cylinder portion 31a of the RI syringe 31 (step 4). In step 4, the first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C each independently detect the radioactivity intensity and input their output values ​​to the control means 35. The control means 35 calculates the average value of the output values ​​of the first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C. Steps 3 and 4 correspond to the detection steps.

[0042] The control means 35 compares the average value calculated in step 4 with a pre-stored target value (step 5), and repeatedly executes steps 3 and 4 until the average value reaches the target value, thereby controlling the amount of suction by the RI syringe 31. If the control means 35 determines that the average value has reached the target value, it instructs the actuator 33 to stop suction by the RI syringe 31 (step 6). Steps 5 and 6 correspond to the suction stop step.

[0043] Next, the fourth RI sensor 47D, fifth RI sensor 47E, and sixth RI sensor 47F of the second detection unit 39 detect (re-detect) the radioactivity intensity of the radioactive liquid stored in the outer cylinder portion 31a of the RI syringe 31, and input the output values ​​to the control means 35. The control means 35 calculates the average value of the output values ​​of the first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C (step 7).

[0044] Next, the control means 35 compares the calculated average value with a pre-stored target value (step 8). If the average value is outside a predetermined error range of the target value, it discharges the radioactive drug solution from the RI syringe 31 in order to discard the radioactive drug solution stored in the RI syringe 31 (step 11). On the other hand, if the average value is within a predetermined error range of the target value, it discharges the radioactive drug solution stored in the outer cylinder 31a from the RI syringe 31 (step 9), and then discharges physiological saline from the saline syringe 27 for administration to the subject (step 10). Steps 9 and 10 correspond to the administration step.

[0045] If a malfunction occurs in the first detection unit 37, the radioactivity intensity of the radioactive drug solution stored in the RI syringe 31 will have a large error compared to the predetermined radioactivity intensity required for administration. In the first administration process described above, the detection accuracy of the first detection unit 37 is indirectly monitored by detecting the radioactivity intensity of the radioactive drug solution with the second detection unit 39, thereby preventing inappropriate administration of the radioactive drug solution.

[0046] Next, with reference to Figure 7, the method of administering the radioactive drug solution according to the procedure for the second administration will be described. As shown in Figure 7, when the second administration is started, the same preparation process (step 21), target value setting input (step 22), aspiration of the radioactive drug solution using the RI syringe 31 (step 23), and detection of the radioactivity intensity of the radioactive drug solution stored in the RI syringe 31 (step 24) are performed as in the first administration. Steps 23 and 24 correspond to the detection steps.

[0047] Next, the control means 35 compares the average value calculated in step 24 with a pre-stored target value (step 25), similar to the first administration process, and repeatedly executes steps 23 and 24 until the average value reaches the target value, thereby controlling the amount aspirated by the RI syringe 31. If the control means 35 determines that the average value has reached the target value, it instructs the actuator 33 to stop aspiration by the RI syringe 31 (step 26). Steps 25 and 26 correspond to the aspiration stop step.

[0048] Subsequently, the control means 35 accepts changes to the target value setting as necessary (step 27). If, for example, the initial setting input was incorrect, the operator operates an operating means (not shown) to input a new target value and correct the target value. When a new target value is input, the control means 35 updates the already stored target value to the new target value. If the target value setting is not changed, the operator operates the operating means to perform an operation indicating no change. Step 27 corresponds to the target value change step.

[0049] Next, immediately before administering the drug to the subject, the fourth RI sensor 47D, fifth RI sensor 47E, and sixth RI sensor 47F of the second detection unit 39 detect (re-detect) the radioactivity intensity of the radioactive drug solution stored in the outer cylinder portion 31a of the RI syringe 31, and input the output values ​​to the control means 35. The control means 35 calculates the average value of the output values ​​of the first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C (step 28). Step 28 corresponds to the re-detection step.

[0050] Next, the control means 35 compares the average value calculated in step 28 with a pre-stored target value (step 29). If the average value is less than the target value, it instructs the actuator 33 to re-aspiration using the RI syringe 31 (step 30). The first detection unit 37 also detects the radioactivity intensity of the radioactive liquid stored in the outer cylinder portion 31a of the RI syringe 31 by re-aspiration and inputs the output value to the control means 35. The control means 35 calculates the average value of the output values ​​of the first RI sensor 47A, the second RI sensor 47B, and the third RI sensor 47C (step 31). Steps 29, 30, and 31 correspond to the adjustment amount detection step.

[0051] Next, the control means 35 compares the average value calculated in step 31 with a pre-stored target value (step 32), and repeatedly executes steps 30 and 31 until the average value reaches the target value. If the control means 35 determines that the average value has reached the target value, it instructs the actuator 33 to stop re-aspiration by the RI syringe 31 (step 33). Step 33 corresponds to the re-aspiration stop step.

[0052] Next, the control means 35 instructs the actuator 33 to discharge the radioactive drug solution stored in the outer cylinder portion 31a (step 34). Furthermore, saline solution is discharged from the saline syringe 27 and administered to the subject (step 35). Steps 34 and 35 correspond to the administration steps.

[0053] The radioactivity intensity of the radioactive drug solution decreases over time. Therefore, after a predetermined time has elapsed between stopping the aspiration of the radioactive drug solution with the RI syringe 31 and administering it to the subject, the radioactivity intensity of the radioactive drug solution may fall below the target value. In the second administration process, the radioactivity concentration is detected in the second detection unit 39 immediately before administration to the subject (step 28). If the average value of the detected values ​​is below the target value, re-aspiration is performed with the RI syringe 31 (step 30) to fine-tune the radioactivity intensity. As a result, in the second administration process, even if the radioactivity intensity of the radioactive drug solution decreases over time, fine-tuning of the radioactivity intensity is possible, making it less wasteful and more efficient to administer the radioactive drug solution compared to discarding and re-aspirationing it.

[0054] Next, the configuration of the radioactive drug administration device 1 according to this embodiment will be described in more detail with reference to Figures 8 and 9. Figure 8 is a plan view showing the container housing structure 100, which is the structure around the vial 6. Figure 9 is a side view of the container housing structure 100. Note that parts of Figures 8 and 9 are shown in cross-section. Figure 8 is a side view of the container housing structure 100. The container housing structure 100 is a structure provided in the first shielding chamber 16 (see also Figure 1). As shown in Figures 8 and 9, the container housing structure 100 comprises the aforementioned vial 6, a shield case 15, a base plate 60, a side wall portion 61, a sliding mechanism 62, and a measuring mechanism 63.

[0055] As described above, vial 6 is a container for holding radioactive liquid. Vial 6 has a main body 70, an inlet 71, and a lid 72. The main body 70 has a bottomed cylindrical shape that extends vertically. The main body 70 has a cylindrical outer wall 70a and a bottom wall 70b. The inlet 71 extends upward from the upper end of the main body 70 and is a portion with a smaller diameter than the main body 70. The lid 72 is a member that closes the opening at the upper end of the inlet 71. The main body 70 and the inlet 71 are made of a material such as glass, and the lid 72 is made of a material such as aluminum or rubber.

[0056] The shield case 15 is a component that shields against radioactivity from the radioactive liquid inside the vial 6. The shield case 15 is made of a material such as tungsten or lead. The shield case 15 comprises a main body 73 and a lid 74. The main body 73 has a housing space 76 for housing the vial 6. The housing space 76 has a cylindrical shape and has an inner circumferential surface 76a that supports the outer circumferential wall 70a of the vial 6 from the outer side, and a bottom surface 76b that supports the bottom wall 70b of the vial 6 from below. The upper end region 77 of the housing space 76 has a larger inner diameter than the region corresponding to the main body 70 and opens upward at the upper end of the shield case 15. Part of the inlet 71 of the vial 6 and the lid 72 are located in the upper end region 77. The upper end region 77 is closed by the lid 74. The center line CL1 of the housing space 76 of the shield case 15 is positioned to be coaxial with the center line of the vial 6 placed in the housing space 76.

[0057] The base plate 60 is a member that supports the shield case 15. The base plate 60 is a plate-shaped member that extends horizontally at a position spaced upward from the bottom surface 16a of the first shielding chamber 16. The base plate 60 is made of a material such as stainless steel. The lower surface 73a of the main body 73 of the shield case 15 is fixed to the upper surface of the base plate 60.

[0058] The side wall portion 61 is a member that further covers the periphery of the shield case 15 on the base plate 60 from the outer edge. The side wall portion 61 is formed of a material such as stainless steel.

[0059] The slide mechanism 62 is a mechanism for sliding the vial 6 into the first shielding chamber 16 of the radioactive drug delivery device 1. The slide mechanism 62 slides the vial 6 in the front-rear direction D1 (see Figure 9). The front side in the front-rear direction D1 is the opening side where the door of the housing 13 (see Figure 1) is provided. For example, in Figures 1 and 8, the front side of the paper is the front side in the front-rear direction. The slide mechanism 62 comprises a slide part 78 and a guide part 79. The slide part 78 is fixed to both ends of the lower surface of the base plate 60 in the left-right direction (horizontal direction perpendicular to the front-rear direction D1). A pair of slide parts 78 are provided so as to extend in the front-rear direction D1 (see Figure 9). The guide part 79 is a member that guides the slide part 78 to slide in the front-rear direction D1. The guide part 79 is fixed to the bottom surface 16a of the first shielding chamber 16 at a position corresponding to each slide part 78. With this configuration, the base plate 60, shield case 15, side wall portion 61, and vial 6 slide together with the slide portion 78 along the guide portion 79 in the front-rear direction D1.

[0060] The measuring mechanism 63 is a mechanism for measuring the yield of radioactive drug solution in the vial 6. The measuring mechanism 63 comprises a sensor 80, a case portion 81, and a protective member 82. The measuring mechanism 63 is located at the bottom of the shield case 15 in which the vial 6 is housed. Specifically, the measuring mechanism 63 is positioned in the space between the bottom surface 16a and the lower surface of the base plate 60, and is fixed to a predetermined position on the bottom surface 16a. With this configuration, the radioactive drug solution dispensing device 1 is configured to have a sensor 80 for measuring the yield of radioactive drug solution in the vial 6 located at the bottom of the shield case 15.

[0061] Any radioactivity sensor capable of measuring the amount of radioactivity can be used as the sensor 80. For example, a photodiode, scintillator, Geiger-Müller counter, ionization chamber, etc., can be used as the sensor 80. The detection surface 80a of the sensor 80 faces upward and is positioned to face the lower surface of the vial 6 in the vertical direction. The sensor 80 is positioned so that its centerline is coaxial with the centerline CL1 of the shield case 15 and the vial 6.

[0062] The case portion 81 houses the sensor 80 in the housing space 81a and is fixed to the bottom surface 16a. Thus, the sensor 80 is fixed to the bottom surface 16a via the case portion 81. The housing space 81a of the case portion 81 is open at its top. The case portion 81 is made of a material such as lead or tungsten. The shape of the case portion 81 is not particularly limited; it may be cylindrical or have a polygonal cylindrical shape such as a square tube. The protective member 82 is a member that protects the sensor 80. The protective member 82 is provided to close the opening at the upper end of the housing space 81a of the case portion 81. Thus, the detection surface 80a of the sensor 80 is covered and protected by the protective member 82. The protective member 82 is made of a material such as acrylic. The upper surface of the protective member 82 is positioned at a distance below the lower surface of the base plate 60. Therefore, a space is formed between the upper surface of the protective member 82 and the lower surface of the base plate 60.

[0063] Here, the sensor 80 measures the yield of the radioactive liquid through a pinhole 90 in the shield case 15. The pinhole 90 is a through-hole that penetrates from the lower surface 73a of the main body 73 to the bottom surface 76b of the containment space 76 at the location where the sensor 80 is positioned horizontally. The inner diameter of the pinhole 90 is not particularly limited, but should be set to a size that can be detected by the sensor 80 while suppressing the leakage of radioactivity from the vial 6 to the outside of the shield case 15, for example, it may be set to 0.5 mm to 4.1 mm. The pinhole 90 is positioned so that its centerline is coaxial with the centerline CL1 of the shield case 15, the vial 6, and the sensor 80.

[0064] With this configuration, radiation RG from the radioactive liquid contained in vial 6 enters the pinhole 90 from the bottom surface 76b of vial 6, passes downward through the pinhole 90, and enters the detection surface 80a of sensor 80 via base plate 60, space, and protective member 82.

[0065] The sensor 80 is fixed to the radioactive drug delivery device 1 by being fixed to the bottom surface 16a. Therefore, the position of the sensor 80 remains unchanged regardless of the sliding movement of the sliding mechanism 62. On the other hand, the pinhole 90 is formed in the shield case 15, so the shield case 15 slides together with the vial 6. The sensor 80 is fixed in a position coaxial with the center line CL1 when the vial 6 is placed at the measurement position PG.

[0066] Next, the operation and effects of the radioactive drug administration device 1 and the radioactive drug administration method according to this embodiment will be described.

[0067] In the radioactive drug dispensing device 1, a sensor 80 for measuring the yield of radioactive drug in vial 6 is provided at the bottom of the shield case 15 in which vial 6 is placed. Therefore, the sensor 80 can measure the yield of radioactive drug in vial 6 while vial 6 remains in the shield case 15. Thus, the sensor 80 can easily measure while suppressing the effects of external radiation by the shield case 15. Furthermore, even if the amount of radioactive drug in vial 6 decreases, the liquid level fluctuates, but the radioactive drug remains accumulated on the bottom surface 76b side of vial 6. Therefore, by measuring from the bottom of the shield case 15, the sensor 80 can perform measurements while suppressing the effects of geometric changes in the object being measured. As a result, the yield of radioactive drug contained in vial 6 can be easily and accurately determined.

[0068] The sensor 80 may measure the yield of the radioactive drug solution through a pinhole 90 in the shielding case 15. In this case, the radiation RG from the vial 6 to the sensor 80 passes through the pinhole 90 in the shielding case 15, suppressing the influence of external radiation, and can be accurately incident on the sensor 80 with directionality while being suppressed to a small amount. Therefore, geometric variations in the measurement target can be suppressed.

[0069] A sliding mechanism 62 is provided at the bottom of the shield case 15, allowing the vial 6 to slide relative to the radioactive drug delivery device 1, and the sensor 80 may be fixed to the radioactive drug delivery device 1. In this case, once the vial 6 has been moved to the measurement position by the sliding mechanism 62, the sensor 80 can perform the measurement.

[0070] The upper part of the sensor 80 may be covered with a protective member 82. In this case, even if the sensor 80 is placed at the bottom of the vial 6, the sensor 80 can be protected from contamination from above by the protective member 82.

[0071] The radioactive drug administration method according to this embodiment is a radioactive drug administration device 1 comprising a vial 6 for containing the radioactive drug and a syringe 31 for aspirating the radioactive drug from the vial 6 and discharging the radioactive drug for administration, wherein the method measures the yield of the radioactive drug in the vial 6, and the yield is measured by a sensor 80 from the bottom of the shield case 15 in which the vial 6 is placed.

[0072] This method of administering radioactive liquid can achieve the same effects and actions as the radioactive liquid administration device 1 described above.

[0073] In this radioactive drug administration device 1, the amount of radioactive drug in vial 6 gradually decreases as administration is repeated, causing the liquid level to drop. For example, if the sensor 80 detects from the side of the shielding case 15, it is not possible to detect fluctuations in the amount of radioactive drug. Also, if a sideways pinhole is formed, it becomes more susceptible to external radiation. If the sensor 80 detects from the top of the shielding case 15, detection becomes difficult because the liquid level moves away from the sensor 80. In contrast, by having the sensor 80 measure from the bottom of vial 6, it is possible to measure even when the amount of radioactive drug in vial 6 has decreased to just before it runs out. Furthermore, because the pinhole 90 extends downwards, even if the radioactive drug in vial 6 leaks, it can flow downwards where the shielding structure is sufficiently effective.

[0074] For example, if a pre-calculated amount of radioactive drug solution is placed in vial 6 and administered, the radioactive drug solution may run out midway through the last dose due to errors in the calculation. In contrast, the radioactive drug solution administration device 1 according to this embodiment can accurately measure the amount of radioactive drug solution for the last one or two doses using the sensor 80. Therefore, it is possible to avoid the situation where the radioactive drug solution runs out midway through the initial administration.

[0075] Furthermore, the radioactive drug solution may be measured using a dose calibrator, and the parameters of the device may be adjusted so that the amount measured by the dose calibrator matches the amount measured by the sensor 80. After calibration is complete, measurements may be performed using the radioactive drug solution dispensing device 1 according to this embodiment.

[0076] The present invention is not limited to the embodiments described above.

[0077] For example, the overall configuration of the radioactive drug administration device is not limited to that shown in Figure 1, and may be modified as appropriate within the scope of the present invention. Furthermore, the flowcharts shown in Figures 6 and 7 are merely examples of processing and may be modified as appropriate. [Explanation of symbols]

[0078] 1...Radioactive drug administration device, 6...Vial (container), 15...Shielding case, 31...Syringe, 62...Slide mechanism, 80...Sensor, 82...Protective component, 90...Pinhole.

Claims

1. A container for holding radioactive liquid, A radioactive drug administration device comprising: a syringe for aspirating the radioactive drug solution from the container and for discharging the radioactive drug solution for administration, A radioactive drug administration device, wherein a sensor for measuring the yield of the radioactive drug solution in the containment container is provided at the bottom of the shield case in which the containment container is placed.

2. The radioactive drug administration device according to claim 1, wherein the sensor measures the yield of the radioactive drug solution through a pinhole in the shield case.

3. A sliding mechanism is provided on the bottom side of the shield case, which allows the containment container to slide relative to the radioactive drug administration device. The radioactive drug delivery device according to claim 1, wherein the sensor is fixed to the radioactive drug delivery device.

4. The radioactive drug administration device according to claim 1, wherein the upper part of the sensor is covered with a protective member.

5. A container for holding radioactive liquid, A radioactive drug administration device comprising a syringe for aspirating the radioactive drug solution from the containment container and for discharging the radioactive drug solution for administration, wherein a method for measuring the yield of the radioactive drug solution in the containment container is provided, A method for measuring radioactive liquid, comprising measuring the yield by a sensor from the bottom of a shield case in which the containment container is placed.

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